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ALGORITHMS, FLUX DENSITY, NEUTRON FLUX, NEUTRON TRANSPORT THEORY, PERTURBATION THEORY, PROMPT NEUTRONS, REACTOR KINETICS EQUATIONS, REACTOR PHYSICS, SPATIAL DISTRIBUTION, TRANSIENTS

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BARYONS, DISTRIBUTION, ELEMENTARY PARTICLES, EQUATIONS, FERMIONS, FISSION NEUTRONS, HADRONS, NEUTRONS, NUCLEONS, RADIATION FLUX, TRANSPORT THEORY

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Reference NumberReference Number

28013914

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GENERAL STUDIES OF NUCLEAR REACTORS (E2200)

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Physical principles of self-protection of reactor cores of nuclear power plants

Usynin, G.B.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Original Title

Fizicheskie printsipy samozashchishchennosti aktivnykh zon YaEhU

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Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 23-24; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

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Miscellaneous

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Conference

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Descriptors (DEI)

REACTIVITY, REACTOR ACCIDENTS, REACTOR CORES, REACTOR SAFETY, RISK ASSESSMENT, SAFETY ANALYSIS

Descriptors (DEC)

ACCIDENTS, REACTOR COMPONENTS, SAFETY

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Reference NumberReference Number

28013943

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SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3200)

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WWER type reactor core modernization to increase the reactor safety

Dukhovenskij, A.S.; Gerasimchuk, O.G.; Proshkin, A.A.; Shestopalov, A.A.
Problems of nuclear reactor safety. Vol. 11995

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[en] Short communication

Original Title

Modernizatsiya aktivnoj zony VVEhR s tsel'yu povysheniya bezopasnosti

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Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 226-228; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

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OPTIMIZATION, REACTOR CORES, REACTOR SAFETY, WWER TYPE REACTORS

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Descriptors (DEC)

ENRICHED URANIUM REACTORS, POWER REACTORS, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTORS, SAFETY, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS

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Reference NumberReference Number

28014179

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GENERAL STUDIES OF NUCLEAR REACTORS (E2100)

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Computerized simulation of reactor with the high heat capacity of reactor core during the accident caused by high positive reactivity insertion

Gol'tsev, A.O.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Original Title

Raschetnoe modelirovanie povedeniya reaktora s bol'shoj teploemkost'yu aktivnoj zony pri avarii vyzvannoj vvodom bol'shoj poozhitelnoj reaktivnosti

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Secondary Subject

SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3300)

Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 144-146; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

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Miscellaneous

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COMPUTERIZED SIMULATION, HEAT TRANSFER, LWGR TYPE REACTORS, REACTIVITY INSERTIONS, REACTOR START-UP, ROD EJECTION ACCIDENTS, SPECIFIC HEAT, TIME DEPENDENCE

Descriptors (DEI)

Descriptors (DEC)

ACCIDENTS, ENERGY TRANSFER, GRAPHITE MODERATED REACTORS, PHYSICAL PROPERTIES, REACTOR ACCIDENTS, REACTORS, SIMULATION, START-UP, THERMODYNAMIC PROPERTIES, WATER COOLED REACTORS

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Reference NumberReference Number

28013924

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GENERAL STUDIES OF NUCLEAR REACTORS (E2100)

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Application of analytical computational systems for simulation of physical processes in nuclear reactors

Fomichenko, P.A.; Boyarinov, V.F.; Vasil'ev, A.V.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Original Title

Primenenie sistem analiticheskikh vychislenij pri modelirovanii fizicheskikh protsessov v yadernykh reaktorakh

Primary Subject

Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 166-168; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

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Miscellaneous

Literature Type

Conference

Report Number

Country of publication

COMPUTERIZED SIMULATION, FINITE DIFFERENCE METHOD, GREEN FUNCTION, M CODES, NEUTRON DIFFUSION EQUATION, NEUTRON TRANSPORT THEORY, PERTURBATION THEORY, REACTOR PHYSICS

Descriptors (DEI)

Descriptors (DEC)

CALCULATION METHODS, COMPUTER CODES, FUNCTIONS, ITERATIVE METHODS, NUMERICAL SOLUTION, SIMULATION, TRANSPORT THEORY

LanguageLanguage

Reference NumberReference Number

28013926

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GENERAL STUDIES OF NUCLEAR REACTORS (E2300)

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Fuel fragmentation and pressure wave generation conditions of reactivity-initiated reactor accidents

Aksenov, R.M.; Afremov, D.A.; Sirotkin, V.K.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Original Title

Fragmentatsiya topliva i generatsiya davleniya v usloviyakh reaktivnostnykh avarij reaktora

Primary Subject

Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 156-158; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

Record Type

Miscellaneous

Literature Type

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Report Number

Country of publication

COMPUTERIZED SIMULATION, FUEL ELEMENT FAILURE, FUEL PARTICLES, FUEL-COOLANT INTERACTIONS, PARTICLE SIZE, REACTIVITY, REACTOR ACCIDENTS

Descriptors (DEI)

Descriptors (DEC)

ACCIDENTS, SIMULATION, SIZE

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Reference NumberReference Number

28014016

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GENERAL STUDIES OF NUCLEAR REACTORS (E2400)

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Integration of error tolerant concept into the design of control room of nuclear power plants

Sepanloo, K.; Meshkati, N.; Moatar, F.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Primary Subject

Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 28-30; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

Record Type

Miscellaneous

Literature Type

Conference

Report Number

Country of publication

ACCIDENTS, CONTROL SYSTEMS, NUCLEAR FACILITIES, POWER PLANTS, THERMAL POWER PLANTS

Descriptors (DEI)

CONTROL ROOMS, HUMAN FACTORS, NUCLEAR POWER PLANTS, REACTOR ACCIDENTS, REACTOR CONTROL SYSTEMS, RELIABILITY, SYSTEMS ANALYSIS, TOLERANCE

Descriptors (DEC)

LanguageLanguage

English

Reference NumberReference Number

28014078

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GENERAL STUDIES OF NUCLEAR REACTORS (E2400)

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Modernization of the standard RBMK control system for prevention of exploitation limit exceeding

Postnikov, V.V.; Zonov, I.V.; Shchukin, N.V.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Original Title

Modernizatsiya shtatnoj sistemy kontrolya reaktorov tipa RBMK dlya predotvrashcheniya prevysheniya ehkspluatatsionnykh predelov

Primary Subject

Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 92-93; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

Record Type

Miscellaneous

Literature Type

Conference

Report Number

Country of publication

COMPUTERIZED CONTROL SYSTEMS, ERRORS, HEAT TRANSFER, LWGR TYPE REACTORS, POWER DISTRIBUTION, REACTOR ACCIDENTS, REACTOR MONITORING SYSTEMS, TEMPERATURE MONITORING, V CODES

Descriptors (DEI)

Descriptors (DEC)

ACCIDENTS, COMPUTER CODES, CONTROL SYSTEMS, DISTRIBUTION, ENERGY TRANSFER, GRAPHITE MODERATED REACTORS, MONITORING, ON-LINE CONTROL SYSTEMS, ON-LINE SYSTEMS, REACTORS, SPATIAL DISTRIBUTION, WATER COOLED REACTORS

LanguageLanguage

Reference NumberReference Number

28014082

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SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3500)

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Application of the similarity theory for optimization of fast reactor safety characteristics

Belov, D.Yu.; Alekseev, P.N.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Original Title

Ispol'zovanie teorii podobiya dlya optimizatsii kharakteristik bezopasnosti bystrykh reaktorov

Primary Subject

Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 53-55; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

Record Type

Miscellaneous

Literature Type

Conference

Report Number

Country of publication

Descriptors (DEI)

ALGORITHMS, CRITICALITY, FAST REACTORS, OPTIMIZATION, PERTURBATION THEORY, REACTIVITY, REACTOR CORES, REACTOR KINETICS, REACTOR SAFETY, SPHERICAL CONFIGURATION

Descriptors (DEC)

CONFIGURATION, EPITHERMAL REACTORS, KINETICS, REACTOR COMPONENTS, REACTORS, SAFETY

LanguageLanguage

Reference NumberReference Number

28014334

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SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3500)

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SUPER PHENIX - core configuration devoted to Pu burning

Varaine, F.; Zaetta, A.; Tommasi, J.
Problems of nuclear reactor safety. Vol. 11995

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AbstractAbstract

[en] Short communication

Primary Subject

Source

Shal'nov, A.V. (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Komitet po Vysshemu Obrazovaniyu, Moscow (Russian Federation); Kontsern ROSEhNERGOATOM, Moscow (Russian Federation); Mezhdunarodnoe Yadernoe Obshchetsvo, Moscow (Russian Federation); Mezhdunarodnyj Nauchno-Tekhnicheskij Tsentr, Moscow (Russian Federation); 250 p; 1995; p. 25-27; 9. topical meeting on problems of nuclear reactor safety; 9-j Seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995

Record Type

Miscellaneous

Literature Type

Conference

Report Number

Country of publication

BREEDER REACTORS, DISTRIBUTION, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, PLUTONIUM REACTORS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, SAFETY, SODIUM COOLED REACTORS, SPATIAL DISTRIBUTION

Descriptors (DEI)

FUEL ASSEMBLIES, PHENIX REACTOR, POWER DISTRIBUTION, REACTIVITY, REACTOR CORES, REACTOR SAFETY

Descriptors (DEC)

LanguageLanguage

English

Reference NumberReference Number

28014333

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